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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
DOE opens funding opportunity for HALEU transport packages
The Department of Energy announced November 19 that up to $16 million is available through a new High-Assay Low-Enrichment Transportation Package funding opportunity to research, develop, and acquire Nuclear Regulatory Commission licensing for transportation of HALEU—using new or modified packages.
Bing Hong, Chao Liu, Taosheng Li, Yongfeng Wang, Yanan Li, Mohamed Mazunga
Nuclear Technology | Volume 201 | Number 2 | February 2018 | Pages 174-179
Technical Paper | doi.org/10.1080/00295450.2017.1406270
Articles are hosted by Taylor and Francis Online.
Long counters are widely used for monitoring neutron fluence owing to their constant response in a wide energy range. In this study, an extended long counter named FDS-LC (FDS Long Counter), having a flat response over a wide neutron energy range from 1 keV to 20 MeV, was developed to monitor high neutron fluence. The geometry and basic structure of FDS-LC was optimized by using Monte Carlo simulations, and it consists of the BF3 thermal neutron counter, the inner and outer polyethylene moderators, borated polyethylene absorption layer, and chromium and lead metal neutron multiplier. The parameters such as the effective center, the energy response, and the angluar response of the FDS-LC were estimated using Super Monte Carlo code. The experimental validation of these parameters were performed by using 241Am-Be source and T(d, n)3He neutron source at the China Institute of Atomic Energy in Beijing. The results showed that the fluctuation of the response in the energy range from 1 keV to 20 MeV was less than 12% and the effective center positions were approximately equal to The comparison of the simulation and experimental results of the angular response function showed good agreement with a maximum deviation less than 15.7%.